Table 1.
Summary of the AI-models developed in ASSAS.
| Data generated with | Physical model(s) replaced by a data-driven surrogate model | Type of model | Systems of the reactor | Phase of the accident | Reactor design |
|---|---|---|---|---|---|
| ASTEC | Thermal-hydraulic | Hybrid | Steam Generators, hot and cold legs, pressurizeur | In-vessel phase | PWR 1300 |
| ASTEC | Initialisation of the numerical solver for thermal-hydraulic | Hybrid | Vessel, primary and secondary circuits | In-vessel phase | PWR 1300 |
| ASTEC | Thermal-hydraulic and core degradation | Hybrid | Reactor pressure vessel | In-vessel phase | PWR 1300 |
| ASTEC | All active models for this phase of the accident: Containment thermal-hydraulics, transport of fission products, core-concrete interaction | Global | All active systems for this phase of the accident: reactor containment building | Ex-vessel phase | PWR 1300 and VVER-1000 |
| MELCOR | All | Global | All | In- and ex-vessel phases | Nordic BWR |
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